ML19312C582: Difference between revisions
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{{#Wiki_filter:u.Eb NUCLOACJ C UWLURhLWW45%iR@ OCCXET NUM 5M | {{#Wiki_filter:u.Eb NUCLOACJ C UWLURhLWW45%iR@ OCCXET NUM 5M | ||
-- ~I | -- ~I C her.u 195 56 .2 6 9 kRO DISTRIBUTION con PART 50 DCCKET MATERIAL | ||
C her.u 195 | |||
56 .2 6 9 | |||
kRO DISTRIBUTION con PART 50 DCCKET MATERIAL | |||
. . FROM: OATS oP OCCqE_ _77 E G Case Duka Pow r Comoany Charlotte, NC OATE mECalvv0 W 0 Parker 9-12-77 | . . FROM: OATS oP OCCqE_ _77 E G Case Duka Pow r Comoany Charlotte, NC OATE mECalvv0 W 0 Parker 9-12-77 | ||
,1M R CNOTCRIZED PRCP INPUT PCMM NUM8ER CP CCPIES RECElv50 2CHIG 6N Al= MNCLASSIPIE D pcCPv / J/W60 bCEtPTION ENCLCSURE Supplemant to BX4-1447 Ocenee 1, Cycle 4 Reload Report September, 1977 .................... | ,1M R CNOTCRIZED PRCP INPUT PCMM NUM8ER CP CCPIES RECElv50 2CHIG 6N Al= MNCLASSIPIE D pcCPv / J/W60 bCEtPTION ENCLCSURE Supplemant to BX4-1447 Ocenee 1, Cycle 4 Reload Report September, 1977 .................... | ||
Line 30: | Line 24: | ||
,.>> ', ,{ ,gg t V | ,.>> ', ,{ ,gg t V | ||
; | ; | ||
A | A n_.-,., _hQ i' J ,,:-- 6p | ||
n_.-,., _hQ i' J ,,:-- 6p | |||
. V a. , vs _,. , y .L.i.. 7 G CL | . V a. , vs _,. , y .L.i.. 7 G CL | ||
.y73g. Oconee #1 | .y73g. Oconee #1 | ||
Line 40: | Line 32: | ||
i I f | i I f | ||
I I w I l | I I w I l | ||
[ T INTERNAL OISTRIEUTION | [ T INTERNAL OISTRIEUTION | ||
, REG FTP # I i l l l l 4 .. PDR l I i l i I&E (2) l I l 4 i I I I OELD I I I RANAUER l l I l l l CHECK i i l i l i STELLO I I I I i EISENHUT i i i i SHA0 I i i I 3AER ! I i l i I iBUTLER l l l l 1 l 1: GRIMES I l l l 1 i 1, J. COLLI.NS i j l l l 1 | , REG FTP # I i l l l l 4 .. PDR l I i l i I&E (2) l I l 4 i I I I OELD I I I RANAUER l l I l l l CHECK i i l i l i STELLO I I I I i EISENHUT i i i i SHA0 I i i I 3AER ! I i l i I iBUTLER l l l l 1 l 1: GRIMES I l l l 1 i 1, J. COLLI.NS i j l l l 1 | ||
Line 52: | Line 43: | ||
-*A& 1OU , | -*A& 1OU , | ||
s | s s | ||
s | |||
DUKE POWER COMPANY | DUKE POWER COMPANY | ||
/ | / | ||
e\ PowEH BtJILDING 422 ' . cTn Cat:acu Srazer Citaat.orTz. N. C. 28242 auw o naa ra. sa. September 8, 1977 bCF Pe E si C E'e ? IE E**0N E: A | e\ PowEH BtJILDING 422 ' . cTn Cat:acu Srazer Citaat.orTz. N. C. 28242 auw o naa ra. sa. September 8, 1977 bCF Pe E si C E'e ? IE E**0N E: A | ||
* f 4 704 | * f 4 704 59 tau Peo ois c+ 0% y 4"* , J 7 J- 40 8 3 | ||
59 tau Peo ois c+ 0% y 4"* , J 7 J- 40 8 3 | |||
,/ i- - i ,. , | ,/ i- - i ,. , | ||
/~ | /~ | ||
Mr. Edson G. Case, Acting Director J Office of Nuclear Reactor Regulation g U. S. Nuclear Regulatory Commission f-M ." , .. | Mr. Edson G. Case, Acting Director J Office of Nuclear Reactor Regulation g U. S. Nuclear Regulatory Commission f-M ." , .. | ||
20555 | 20555 | ||
* Washington, D. C. - | * Washington, D. C. - | ||
Line 80: | Line 60: | ||
By letter of March 30, 1977, we submitted proposed Technical Specification changes and the supporting reload report applicable to Oconee 1 Cycle 4. | By letter of March 30, 1977, we submitted proposed Technical Specification changes and the supporting reload report applicable to Oconee 1 Cycle 4. | ||
This submittal was supplemented by our letter of August 23, 1977, to take into account the operation of Cycle 3 up to 308 EFPD. During the refueling operation, however, fuel assembly 1D40, a Batch 4 fuel assembly intended to undergo Cycle 4 operation in core location N-12, was damaged while it was being examined in the Post Irradiation Examination facility. The nature of the damage was s ch that the upper portion of a corner fuel rod was displaced from the upper fuel assembly skirt and as such is considered unsuitable for re-insertion into the core. Therefore, this fuel assembly is to be replaced by a once-burned Batch 2 fuel assembly. Because of this replacement, three other Batch 4 fuel assemblies in 1/4-core-symmetric locations are to be replaced with Batch 2 assemblies to maintain core s mmietry. | This submittal was supplemented by our letter of August 23, 1977, to take into account the operation of Cycle 3 up to 308 EFPD. During the refueling operation, however, fuel assembly 1D40, a Batch 4 fuel assembly intended to undergo Cycle 4 operation in core location N-12, was damaged while it was being examined in the Post Irradiation Examination facility. The nature of the damage was s ch that the upper portion of a corner fuel rod was displaced from the upper fuel assembly skirt and as such is considered unsuitable for re-insertion into the core. Therefore, this fuel assembly is to be replaced by a once-burned Batch 2 fuel assembly. Because of this replacement, three other Batch 4 fuel assemblies in 1/4-core-symmetric locations are to be replaced with Batch 2 assemblies to maintain core s mmietry. | ||
The nuclear, mechanical, thermal-hydraulic and safety considerations of the substitution of four Batch 2 assemblies for the Batch 4 assemblies have been evaluated, and 't has been determined that the conclusions re- | The nuclear, mechanical, thermal-hydraulic and safety considerations of the substitution of four Batch 2 assemblies for the Batch 4 assemblies have been evaluated, and 't has been determined that the conclusions re-garding the safety of Cycle 4 operation as described in the reload report (BAW-1447, March 1977) are unaffected by the modified core loading. | ||
garding the safety of Cycle 4 operation as described in the reload report (BAW-1447, March 1977) are unaffected by the modified core loading. | |||
Furthermore, it has been deternined that no changes are required for the Technical Specifications previously established for Cycle 4 operation. | Furthermore, it has been deternined that no changes are required for the Technical Specifications previously established for Cycle 4 operation. | ||
The attached report provides additional details cf the modified core load-ing and supplements the information provided in the reload report. | The attached report provides additional details cf the modified core load-ing and supplements the information provided in the reload report. | ||
Line 89: | Line 67: | ||
,l ) ~ n t . l.b . /~ | ,l ) ~ n t . l.b . /~ | ||
Jilliam O. Parker, Jr./ | Jilliam O. Parker, Jr./ | ||
v, PMA:ge Attachment | v, PMA:ge Attachment t}} | ||
t}} |
Revision as of 09:49, 1 February 2020
ML19312C582 | |
Person / Time | |
---|---|
Site: | Oconee ![]() |
Issue date: | 09/08/1977 |
From: | Parker W DUKE POWER CO. |
To: | Case E Office of Nuclear Reactor Regulation |
Shared Package | |
ML19312C583 | List: |
References | |
NUDOCS 7912180889 | |
Download: ML19312C582 (2) | |
Text
u.Eb NUCLOACJ C UWLURhLWW45%iR@ OCCXET NUM 5M
-- ~I C her.u 195 56 .2 6 9 kRO DISTRIBUTION con PART 50 DCCKET MATERIAL
. . FROM: OATS oP OCCqE_ _77 E G Case Duka Pow r Comoany Charlotte, NC OATE mECalvv0 W 0 Parker 9-12-77
,1M R CNOTCRIZED PRCP INPUT PCMM NUM8ER CP CCPIES RECElv50 2CHIG 6N Al= MNCLASSIPIE D pcCPv / J/W60 bCEtPTION ENCLCSURE Supplemant to BX4-1447 Ocenee 1, Cycle 4 Reload Report September, 1977 ....................
submitted in support of their 3-30-77 raquast p . ".' , for tech specs change .
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A n_.-,., _hQ i' J ,,:-- 6p
. V a. , vs _,. , y .L.i.. 7 G CL
.y73g. Oconee #1
. ,9-13 77 ahf I
I SA7 Err FOR ACTION /INFORMATION eRANCH Care 7: m i Jo#weseddb I !
I I I l i l
i I f
I I w I l
[ T INTERNAL OISTRIEUTION
, REG FTP # I i l l l l 4 .. PDR l I i l i I&E (2) l I l 4 i I I I OELD I I I RANAUER l l I l l l CHECK i i l i l i STELLO I I I I i EISENHUT i i i i SHA0 I i i I 3AER ! I i l i I iBUTLER l l l l 1 l 1: GRIMES I l l l 1 i 1, J. COLLI.NS i j l l l 1
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SIC I I I &na ---
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-*A& 1OU ,
s s
DUKE POWER COMPANY
/
e\ PowEH BtJILDING 422 ' . cTn Cat:acu Srazer Citaat.orTz. N. C. 28242 auw o naa ra. sa. September 8, 1977 bCF Pe E si C E'e ? IE E**0N E: A
- f 4 704 59 tau Peo ois c+ 0% y 4"* , J 7 J- 40 8 3
,/ i- - i ,. ,
/~
Mr. Edson G. Case, Acting Director J Office of Nuclear Reactor Regulation g U. S. Nuclear Regulatory Commission f-M ." , ..
20555
- Washington, D. C. -
RE: Oconee Unit 1 s, ,
Docket No. 50 g h ,
Dear Mr. Case:
By letter of March 30, 1977, we submitted proposed Technical Specification changes and the supporting reload report applicable to Oconee 1 Cycle 4.
This submittal was supplemented by our letter of August 23, 1977, to take into account the operation of Cycle 3 up to 308 EFPD. During the refueling operation, however, fuel assembly 1D40, a Batch 4 fuel assembly intended to undergo Cycle 4 operation in core location N-12, was damaged while it was being examined in the Post Irradiation Examination facility. The nature of the damage was s ch that the upper portion of a corner fuel rod was displaced from the upper fuel assembly skirt and as such is considered unsuitable for re-insertion into the core. Therefore, this fuel assembly is to be replaced by a once-burned Batch 2 fuel assembly. Because of this replacement, three other Batch 4 fuel assemblies in 1/4-core-symmetric locations are to be replaced with Batch 2 assemblies to maintain core s mmietry.
The nuclear, mechanical, thermal-hydraulic and safety considerations of the substitution of four Batch 2 assemblies for the Batch 4 assemblies have been evaluated, and 't has been determined that the conclusions re-garding the safety of Cycle 4 operation as described in the reload report (BAW-1447, March 1977) are unaffected by the modified core loading.
Furthermore, it has been deternined that no changes are required for the Technical Specifications previously established for Cycle 4 operation.
The attached report provides additional details cf the modified core load-ing and supplements the information provided in the reload report.
Very uly yours,
. / ~
,l ) ~ n t . l.b . /~
Jilliam O. Parker, Jr./
v, PMA:ge Attachment t